[en] The IAEA defines a strong safety culture as the assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, protection and safety issues receive the attention warranted by their significance. SCPQ-LH is one of the data collection methods, developed by IAEA to assess safety culture in a facility. This study is conducted to understand the safety culture in Nuclear Malaysia using SCPQ-LH via sharepoint Nuclear Malaysia using descriptive analysis. 70 % of the staff works in Nuclear Malaysia had responded to the SCPQ-LH. The results showed that 74 % of the respondents agree that Nuclear Malaysia has a good safety culture. Further studies should be performed to study the correlation between safety culture, various division, year of services, and also to include other four data collection method developed by IAEA to support the finding. (author)

[en] Radiological Impact Assessments (RIAs) on proposed disposal sites for NORM wastes were performed in Malaysia. Analysis results were used to derive site specific guidelines for allowable residual concentrations of radionuclides in soil, calculation of doses and risks. Appropriate use scenarios and site specific parameters were used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Disposals were performed to fulfil Atomic Energy Licensing Board of Malaysia (AELB) requirements for which the operator must carry out a radiological impact assessment. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Fatal cancer risk factor is 5x10^-2 per man.Sv. Radionuclides of main concern are radium-226 and radium-228 which are considered as toxic. Sensitivity and uncertainty analyses were performed to show that the parameters used as input into the computer model were justified so as to improve confidence of the public and the AELB in respect of the results of the analysis. Case study to determine a proposed near surface disposal site for treated oil sludge was described. (author)

[en] A study to determine whether Radiological Impact Assessment (RIA) is needed for landfill disposal of treated sludge (slag) from oil and gas industries has been carried out. Radioactivity level of slag and soil samples have been measured using gamma spectrometry system and its Total Activity Concentration (TAC) has been calculated. It was found that TAC (inclusive background) was within the control limit set by the AELB for example, 3 Bq/g as stipulated in LEM/TEK 58 (AELB, 2009). Therefore, as a result from this study, RIA is not required and the allocated area can be used for the landfill disposal of treated sludge (slag).(author)

[en] The indoor and outdoor radon concentrations in Cameron Highlands (Peninsular Malaysia) and Ranau (East Malaysia) were measured. The measurements were carried out using passive method based on CR-39 solid state nuclear track detector (SSNTD) (for indoor measurements in Cameron Highlands) and active method using continuous radon/ thoron progeny monitor (for indoor and outdoor measurements in Ranau and outdoor measurements in Cameron Highlands). The mean indoor radon concentrations in Cameron Highlands and Ranau were 50 Bqm^-3 and 1.5 Bqm^-3, respectively. The mean indoor radon concentration in Cameron Highlands was slightly higher compare to the world average. The maximum value recorded was 97 Bqm^-3 which is almost similar to WHO reference level. The mean outdoor radon concentrations in Cameron Highlands and Ranau were 7.4 Bqm^-3 and 1.7 Bqm^-3, respectively. The outdoor concentrations were low and comparable to world outdoor average. (author)

[en] The IAEA defines a strong safety culture as the assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, protection and safety issues receive the attention warranted by their significance. Many methods had been developed since Chernobyl accident in 1986 and this continues today, to include the lesson learnt from the Fukushima Daiichi accident in order to identify the safety culture of an organization, however, little studies have been conducted to understand the safety culture in Malaysian Nuclear Agency (Nuclear Malaysia). This study is conducted to understand the safety culture in Nuclear Malaysia using SCPQ-LH via intranet system. The interpretation of the self-assessments requires over 70 % response rate to avoid systematic bias. The results will be analysed using statistical method - descriptive analysis. (author)

[en] Radiological Impact Assessment (RIA) can be conducted in Malaysia by using the RESRAD computer code developed by Argonne National Laboratory, U.S.A. The code can do analysis to derive site specific guidelines for allowable residual concentrations of radionuclides in soil. Concepts of the RIA in the context of waste management concern in Malaysia, some regulatory information and assess status of data collection are shown. Appropriate use scenarios and site specific parameters are used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Case study have been conducted to fulfil Atomic Energy Licensing Board (AELB) requirements where for disposal purpose the operator must be required to carry out. a radiological impact assessment to all proposed disposals. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Results obtained from analyses show the RESRAD computer code is able to calculate doses, risks, and guideline values. Sensitivity analysis by the computer code shows that the parameters used as input are justified so as to improve confidence to the public and the AELB the results of the analysis. The computer code can also be used as an initial assessment to conduct screening assessment in order to determine a proper disposal site. (Author)

[en] The concentration of radon and thoron in water in the vicinity of Lynas Plant in Gebeng Industrial Estate (GIE), Pahang has been measured. The measurements involved surface water and ground water. The water samples have been collected at waste water discharge point, small stream, river and boreholes. The measurements were performed onsite. The results of the measurements showed that the radon concentrations in all types of water were low. The mean radon concentrations in discharge water, surface water and ground water were 0.13 Bq/ L, 0.55 Bq/ L and 1.46 Bq/ L respectively. These values were very far lower than reference level for drinking water set by the World Health Organization (WHO) for example, 100 Bq/ L. There was no thoron detected in all water samples. The effective dose from drinking water containing radon around GIE was very low for example, 1.7 μSv/ y. The public only received dose from natural sources. Lynas operation did not enhance radon activity in water around GIE. (author)

[en] Combined treatment methods were conducted to treat waste streams containing soluble uranium, thorium and radium. Chemical and soil column treatment resulted good decontamination of the waste streams. The initial concentration of uranium and thorium was 49.4 μg/L and 4.64 μg/L, respectively. Initial radium radioactivity counts of fifteen ml was 0.0781 cps. By chemical treatment, percentage removal of uranium, thorium and radium from the waste streams were nearly 100% at the optimum pH 9.9. Comparison of decontamination factors for radium, thorium and uranium has value of 391, 234 and 80, respectively. At pH 9.9, thorium hydroxide (Th(OH)₄⁰) species were the dominant species which form precipitate. For uranium, hexavalent species dominate in the solution. In absence of carbonate the solubility limiting species in oxic systems was U0₂(OH)₂ which were in solid form. Radium precipitated as radium sulphate. The supernatant collected after been separated from the various precipitate showed very low concentration compared from the initial concentration before treatment. Waste streams or supernatants collected from the chemical treatment and pH adjusted to pH 4.0, and then passing through the soil column shows no concentration results of the 3 radionuclides. The retaining radionuclides were adsorbed by the soil column. (author)

[en] This study aims to assess radon/ thoron concentrations and the potential risks of exposure to the public from the Lynas rare-earth processing plant operation in the Gebeng Industrial Estate (GIE), Pahang. The concentrations of radon and thoron in air and water (surface and ground) have been measured within a radius of 3 km from the plant. Based on the finding in this study, it can be concluded that the mean radon and thoron equivalent equilibrium concentration (EEC) in the GIE area were low for example, 6.5 and 2.5 Bq/ m³ respectively. These values were equivalent to values measured outside the GIE area. The mean radon concentration in water in the GIE area was about 1 Bq/ L which is very far below the WHO (2011) reference level for drinking water. There was no thoron detected in all sources of water around the GIE. Overall, there was no enhancement of radon/ thoron concentrations in air and water in the GIE due to activities carried out by Lynas. The public only received a dose from natural background radiation sources. The effective dose received by the public from exposure to radon/ thoron in air and water was 0.3 mSv/ y. The results indicated that no radiological hazard to the people living in the vicinity of the Lynas rare-earth processing plants. (author)

[en] The disposal of amang (tin tailings), a potential naturally occurring radioactive material (NORM) wastes, in this study was modelled to evaluate potential radiological doses to general public by using RESRAD computer code developed by Argonne National Laboratory, USA. An arbitrary study on a site, which has an area of 8000 m² with 0.4 m thickness of amang to be disposed where 2400 m² of the area are used to build a factory or a house. The radiological criteria used are 1 mSv/y for individual member of public and 1 man.Sv for collective dose for population. The input parameters are based on assumed and best available data, thus dose estimated from this assessment are valid with the input data used. The mean value for radioactivity and distribution coefficient of radium in amang was performed and analysed. Four scenarios were used in the assessment. For scenario 1, a factory was built directly on the amang wastes with a concrete slab directly over it. Scenario 2, same construction practice as scenario 1 but an additional clean soil cover above the amang waste before concrete slab, where thickness of soil cover used were 0.2 meter. Both of the scenarios assumed 250 workers working for 2000 hours in a year. Scenario 3, for a house built directly on the amang wastes with concrete slab directly over it. Scenario 4, same construction practice as scenario 3 but an additional clean soil cover above the amang waste before the concrete slab, where thickness of soil cover used were 1.2 meter. Both of the scenarios assumed 6 persons staying inside for maximum 20 hours in a day. The maximum total dose obtained from scenario 1, 2, 3 and 4 in the assessment were 1.2, 0.26, 5.6 and 0.33 mSv/y respectively. The collective doses for scenario 1 to scenario 4 were 0.3, 0.07, 0.04 and 0.003 man.Sv respectively. Scenario 1 and 3 were above the limit for the total dose obtained and scenario 2 and 4 were below the limit. As for collective dose all the four scenarios were below the limit. For safety purpose and compliance with the limit set by authority, scenario 2 and 4 are preferred. (Author)